The Main Steamline Break Transient Analysis for Advanced Boiling Water Reactor Using TRACE, PARCS, and SNAP Codes
To confirm the reactor and containment integrity of the Advanced Boiling Water Reactor (ABWR), we perform the analysis of main steamline break (MSLB) transient by using the TRACE, PARCS, and SNAP codes. The process of the research has four steps. First, the ABWR nuclear power plant (NPP) model is developed by using the above codes. Second, the steady state analysis is performed by using this model. Third, the ABWR model is used to run the analysis of MSLB transient. Fourth, the predictions of TRACE and PARCS are compared with the data of FSAR. The results of TRACE/PARCS and FSAR are similar. According to the TRACE/PARCS results, the reactor and containment integrity of ABWR can be maintained in a safe condition for MSLB.
Digital Object Identifier (DOI): doi.org/10.5281/zenodo.2021695Procedia APA BibTeX Chicago EndNote Harvard JSON MLA RIS XML ISO 690 PDF Downloads 554
 U. S. NRC, TRACE V5.840 user’s manual, 2014.
 T. Downar, Y. Xu, V. Seker, D. Carlson, PARCS v2.7 U.S. NRC Core Neutronics Simulator, 2008.
 Applied Programming Technology, Inc., Symbolic nuclear analysis package (SNAP) user's manual, 2012.
 Taiwan Power Company, Final Safety Analysis Report for Lungmen Nuclear Power Station Units 1&2 (FSAR), Chapter 15, 2007.
 L. S. Kao, J. R. Wang, R. Y. Yuann, W. H. Tung, J.A. Jing, C. T. Lin, Parallel calculations and verifications of limiting transient analyses for Lungmen nuclear power plant, INER-A1609R, 2008.
 L. S. Kao, J. R. Wang, J. R. Tang, J. A. Jing, W. H. Tung, R. Y. Yuann, C. T. Lin, H. T. Lin, Development of Lungmen ABWR Thermal hydraulic Safety analysis Method-The Summary Report, INER-A1742R, 2008.